Draft Safety Evaluation Report Related to "Justification for Not Including Postulated Breaks in Large-Bore Reactor Coolant System Piping in the Licensing Basis for Existing and Replacement Once-Through Steam Generators" (BAW-2374, Rev. 0, July 2000)

DRAFT SAFETY EVALUATION REPORT RELATED TO "JUSTIFICATION FOR NOT INCLUDING POSTULATED BREAKS IN LARGE-BORE REACTOR COOLANT SYSTEM PIPING IN THE LICENSING BASIS FOR EXISTING AND REPLACEMENT ONCE-THROUGH STEAM GENERATORS" (BAW-2374, REV. 0, JULY 2000)

During the 477th meeting of the Advisory Committee on Reactor Safeguards, November 2-4, 2000, the Committee considered the draft safety evaluation report and decided not to review it.

References:

U.S. Nuclear Regulatory Commission Draft Safety Evaluation Report Related to "Justification for Not Including Postulated Breaks in Large-Bore Reactor Coolant System Piping in the Licensing Basis for Existing and Replacement Once-through Steam Generators" (BAW-2374, Rev. 0, July 2000), dated October 27, 2000.